炉内構造物の予防保全に向けた照射誘起応力腐食割れ挙動に与える残留応力の影響評価手法の検討
Study on preventive maintenance of core structural components by evaluating the influence ofresidual stress on irradiation assisted stress corrosion cracking behavior
著者:
三輪 幸夫 Yukio MIWA 近藤 啓悦 Keietsu KONDO 大久保 成彰 Nariaki OKUBO 加治 芳行 Yoshiyuki KAJI
発刊日:
公開日:
core structural materialdamage occurrenceIASCCpreventive maintenanceradiation hardeningradiation-induced segregationradiation-induced stress relaxationresidual stress
概要
This study proposed an evaluation method of damage occurrence of core structural materials by simulation model. Irradiation assisted stress corrosion cracking (IASCC) is one of the damage modes among aged core components. IASCC was thou ght to be caused by material degradation such as losses of workability due to radiation hardening and corrosion resistance due to radiation-induced segregation and residual stress due to welding, then the influence of residual stress on both radiation hardening and radiation induced segregation was examined by ion-irradiation experiments. Not only the residual stress change due to radiation creep was affected by residual stress and dose, but also the material degradati on was affected. This was modeled and the damage occurrence by IASCC in a shroud type component during reactor operating life was estimated by means of FEM calculation based on the models of the material degradation and residual stress.
